Since 18 of December 2019 conferences.iaea.org uses Nucleus credentials. Visit our help pages for information on how to Register and Sign-in using Nucleus.

9–12 Dec 2025
Cambridge, Massachusetts, USA
Europe/Vienna timezone
We’re now accepting invited abstracts only. Stay tuned — the programme will be announced soon!

Coupled Neutronics–CFD Workflow for ARC Tokamak Blanket and Coolant Design

10 Dec 2025, 11:20
25m
Cambridge, Massachusetts, USA

Cambridge, Massachusetts, USA

Hacker Reactor at MIT’s iHQ. Address: 292 Main Street | MIT Bldg. E38 | Floor 7 |Cambridge, MA 02142
Oral Simulation and Modelling Techniques Simulation and Modelling Techniques

Speaker

Austin Carter (Commonwealth Fusion Systems)

Description

The ARC tokamak is a compact, high-field fusion pilot plant being designed by Commonwealth Fusion Systems to produce net electricity with high-temperature superconducting magnets. It uses a molten salt, FLiBe blanket for tritium breeding and heat removal in a simplified, high-performance design.
We present a multiphysics digital engineering workflow that integrates mesh-based Monte Carlo neutronics (MCNP6) with ANSYS CFD to support increasingly detailed design of ARC’s blanket, vessel, and coolant systems. The workflow couples nuclear heating maps from MCNP6 with thermal–hydraulic simulations: heating distributions inform FLiBe flow requirements, while CFD returns temperature and velocity fields that guide material selection, structural optimization, and flow path design. Beyond heat transport, the workflow also models the generation and circulation of activation products within the FLiBe, particularly important isotopes such as N-16, F-18, F-20, and O-19. These short-lived radionuclides create a moving source term that extends outside the tokamak into the balance-of-plant, particularly at heat exchangers with the secondary nitrate salt loop. By linking neutronics with CFD, the workflow enables steady-state mapping of isotope distributions and the resulting dose fields throughout the facility. Since activated salt requires radiation shielding and contributes significantly to the plant’s external source term, it is advantageous to minimize radionuclide concentrations leaving the vessel. The workflow addresses this optimization challenge by providing a means to evaluate and design flow paths that maximize in-vessel decay before the coolant exits the machine.
This paper describes the architecture of the data exchange and solver coupling, and presents preliminary results that highlight the potential of integrated multiphysics workflows to accelerate fusion power plant design while providing a more complete picture of nuclear heating, coolant performance, and radiological safety.

Country or International Organisation United States of America
Affiliation Commonwealth Fusion Systems
Speaker's email address acarter@cfs.energy

Author

Austin Carter (Commonwealth Fusion Systems)

Co-authors

Dr Hao Wu (Commonwealth Fusion Systems) Ms Katie Saltzgiver (Commonwealth Fusion Systems) Mr Kimbal Hall (Commonwealth Fusion Systems) Dr Ryanne Kennedy (Commonwealth Fusion Systems)

Presentation materials

There are no materials yet.